发明名称
摘要 <p><P>PROBLEM TO BE SOLVED: To sample radioactive powder generated in a spent nuclear fuel reprocessing process without exerting a bad influence on a reprocessing facility or safety. <P>SOLUTION: A constitution is adopted, wherein a sampling device 20 sealed by a casing 10 is mounted on a residue recovery container 5 of a spent nuclear fuel reprocessing facility through a guide pipe 22, and a separation device 21 for opening/closing a conduit is provided on the guide pipe 22, and an injection facility for inert gas (for example, argon gas) is connected to the casing 10, and the inside of the casing 10 is kept so as to have a higher pressure than the inner pressure of the residue recovery container 5 by the argon gas pressure. When inserting a sampler of the sampling device 20 into the residue recovery container 5 through the guide pipe 22 from inside the casing 10 by opening the separation device 21, and capturing radioactive powder into the sampler, leakage of an atmosphere in the residue recovery container 5 to the casing 10 side is blocked by the argon gas pressure, and further the atmosphere in the casing can be replaced with argon gas so that moisture does not enter the residue recovery container 5 from the casing 10 side. <P>COPYRIGHT: (C)2011,JPO&INPIT</p>
申请公布号 JP5124548(B2) 申请公布日期 2013.01.23
申请号 JP20090204250 申请日期 2009.09.04
申请人 发明人
分类号 G01N1/04;G01T7/02;G21C19/44 主分类号 G01N1/04
代理机构 代理人
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